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Front-end nuclear fuel supply cooperation: Turning allied interdependence into strategic advantage
The global nuclear revival, which is fueled by unprecedented demand for firm, affordable, dispatchable power for artificial intelligence and data center build-out, energy security imperatives, and climate commitments, has exposed a structural reality of the Western fuel cycle: No single allied nation currently possesses the full suite of front-end capabilities. From mining through conversion, enrichment, fabrication, and the emerging deconversion and metallization steps required for reactor fuels, capability is distributed across Canada, France, Japan, the United Kingdom, and the United States (collectively, the “Sapporo Five”), as well as a small group of close partners.
L. Srinivasan
Nuclear Science and Engineering | Volume 79 | Number 2 | October 1981 | Pages 228-233
Technical Note | doi.org/10.13182/NSE81-A27411
Articles are hosted by Taylor and Francis Online.
A new numerical approach is attempted to solve the three-dimensional multigroup diffusion equation in rectangular geometry using the principles of variational calculus. The method essentially consists in separating the variables along the x, y, and z directions so that the neutron flux can be synthesized into three components to get an approximate solution. This solution can be used as a starting trial function for flux in the next step, where the variables are treated nonseparable in order to get a better solution. The effect of separation of variables is also studied. Detailed calculations are performed for a benchmark problem and the results are presented along with published values that are calculated using finite difference codes.